ML20213F093

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Forwards Reactor Sys Branch Input to Sser 28.Input Includes Updated Info on Allegation 45.Evaluation Reflects Info in Util .Salp Evaluation Also Encl
ML20213F093
Person / Time
Site: Diablo Canyon Pacific Gas & Electric icon.png
Issue date: 12/14/1984
From: Houston R
Office of Nuclear Reactor Regulation
To: Novak T
Office of Nuclear Reactor Regulation
Shared Package
ML20213D572 List:
References
FOIA-84-741, FOIA-84-742 NUDOCS 8412260080
Download: ML20213F093 (3)


Text

aP OEC 14 1984 MEMORANDUM FOR:

Thomas M. Novak, Assistant Director for Licensing, DL FROM R. Wayne Houston, Assistant Director for Reactor Safety, DSI

SUBJECT:

DIABLO CANYON NUCLEAR POWER PLANT, UNIT 1 - SER SUPPLEMENT NO. 28 Plant Name:

Diablo Canyon, Unit 1 Docket Number 50-275 Licensing Stage:

OR Responsible Branch: Licensing Branch No. 3 Project Manager:

H. Schierling DSI Review Branch:

Reactor Systems Branch to this memo provides Reactor Systems Branch inputs to Diablo Canyon Unit 1 SSER No. 28.

This input includes updated information on the allegation No. 45.

Our evaluation reflects information in the PGE letter dated September 5, 1984. contains the staff SALP evaluation.

004 :"1 CD,1:1Cy E.W::PO lh:D: ton R. Wayne Houston, Assistant Director for Reactor Safety Division of Systems Integration

Enclosure:

As stated cc:

R. Bernero F. Rosa G. Knighton H. Schierling RSB S/L's S. Diab CONTACT:

C. Liang, RSB X24754 0FFICIAL RECORD COPY

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MEMORANDUM FOR:

Thomas M. Novak, Assistant Director for Licensing, DL FROM R. Wayne Houston, Assistant Director for Reactor Safety, DSI

SUBJECT:

DIABLO CANYON NUCLEAR POWER PLANT, UNIT 1 - SER SUPPLEMENT NO. 28 Plant Name:

Diablo Canyon, Unit 1 Docket Number 50-275 Licensing Stage:

OR Responsible Branch: Licensing Branch No. 3 Project Manager:

H. Schierling DSI Review Branch:

Reactor Systems Branch to this memo provides Reactor Systems Branch inputs to Diablo Canyon Unit 1 SSER No. 28.

This input includes updated information on the allegation No. 45.

Our evaluation reflect information 'n the PGE letter dated September 5, 1984. contains the staff SALP evaluation.

/

Wayne Houston, Assistant Director for Reactor Safety Division of Systems Integration

Enclosure:

As stated cc:

R. Bernero F. Rosa G. Kni.ghton H. Schierling RSB S/L's S. Diab CONTACT:

C. Liang, SB X24754 0FFICIAL RECORD COPY DSI:RSB 6-DSI:RSB DSI:RSB DSI:AD:RS DISTRIBUTION CLiang: Je LMarsh BSheron RWHouston Docket File 12/,e / 4 12/ /84 12/ /84 12/ /84 RSB P/F: DCanyon RSB R/F CLiang R/F CLiang LMarsh

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ENCLOSURE 1 DIABLO CANYON UNIT NO. 1 SSER NO. 28 (R$B)

Task:

A11ecation 45 (Previously addressed in SSERs 21, 22 and 26)

ATS No.:

RV 83A47 BN No.: 83-169 (10/20/83)

Characteri:ation Previously addressed in SSERs 21, 22 and 26.

Imolied Sionificance to Plant Design, Construction, or Ooeration Previously addressed in SSERs 21 and 22.

Assessment of Safety Sionificance Previously addressed in SSERs 21, 22, and 26.

Action Reouired In the staff SSER No. 26, the staff stated that in a letter from G. Knighton (NRC) to J. O. Schuyler (PGE) dated May 21, 1984, tho staff requested that Technical Specification 3.4.9.3 and Operating Procedure B-2.11 be changed within 3 months after the low flow alarm is installed to reauire power to be available to the RHR hot leg suction isolation valves.

5SER No. 26 also stated that the staff would report the resolution of this action item in a later SSER.

In response to this staff requirement, PG and E in it's letter dated September 5, 1984, stated that PG and E has modified the Operating Procedure B-2 series to require that power be applied to the RHR suction valves when in Mode 4 (with the RHR system aligned to the RCS), 5, and 6.

The plant is being oper-ated in a mode that complies with existing Technical Specifications, in that with power applied to the suction valve operators, in modes 4 (below 323*F), 5, and 6 with the head on the vessel, the reciprocating charging pump will not be operated.

Therefore, the change to Technical Specification 4.4.9.3.1, which was also requested in the May 21, 1984, NRC letter, is not required.

The staff has evaluated PG and E's response as stated above and concludes that it is acceptable.

The components which provide the low flow alarm were in-stalled and tested prior to June 6, 1984, as confirmed in a PG and E letter dated June 6, 1984. The licensee has completed the required change of its operating procedure to require power to be available to the RHR hot leg suction valves within three months after the low flow alarm is installed.

Therefore, the staff concludes that no further action is required.

Region V will inspect the licensee's operating procedure relative to this item through the routine inspection program.

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